教授 博士生导师 硕士生导师
任职 : 三束材料改性教育部重点实验室主任
性别: 男
毕业院校: 南京大学
学位: 博士
所在单位: 物理学院
学科: 凝聚态物理
电子邮箱: zhaojj@dlut.edu.cn
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论文类型: 期刊论文
发表时间: 2011-01-01
发表刊物: FUSION ENGINEERING AND DESIGN
收录刊物: SCIE、EI
卷号: 86
期号: 1
页面范围: 45-50
ISSN号: 0920-3796
关键字: First wall; Neutron heating; Plasma heating; Thermal stress
摘要: To understand the combined effect of plasma heating and neutron heating loadings, the distributions of temperature, stress, and strain in different two-dimensional first wall panel models under normal ITER operation condition were simulated using finite element method. The maximum temperature occurs at the Be armor, and reaches 461 degrees C. High thermal stresses (in the range of 80-200 MPa) are found at the interface between the Be armor and the CuCrZr layer. The maximum thermal stress reaches 324 MPa in the SS316L cooling tube (20 mm diameter), exceeding its yield strength and resulting in a maximum strain of about 1.7% at the tube inner surface. These simulation results are useful for the design and operation of ITER. (C) 2010 Elsevier B.V. All rights reserved.